JPS59159097A - Coolant degassing device in light water reactor - Google Patents

Coolant degassing device in light water reactor

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Publication number
JPS59159097A
JPS59159097A JP58032927A JP3292783A JPS59159097A JP S59159097 A JPS59159097 A JP S59159097A JP 58032927 A JP58032927 A JP 58032927A JP 3292783 A JP3292783 A JP 3292783A JP S59159097 A JPS59159097 A JP S59159097A
Authority
JP
Japan
Prior art keywords
coolant
gas
condenser
steam
line
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
JP58032927A
Other languages
Japanese (ja)
Inventor
西原 幸夫
「峰」元 雅樹
船越 俊男
直幸 上島
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP58032927A priority Critical patent/JPS59159097A/en
Publication of JPS59159097A publication Critical patent/JPS59159097A/en
Pending legal-status Critical Current

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Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Physical Water Treatments (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 本発明は軽水炉の冷却材脱ガス装置に関するものである
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a coolant degassing device for a light water reactor.

従来の軽水炉の冷却材脱ガス装置を第1.2図に示した
。まず第1図の冷却材脱ガス装置を説明すると、(α)
が原子炉の一次冷却系に接続した冷り材抽出ライン、(
h)が体積制御タンク、(’1)(’2)がガス圧縮機
、(d)が水素分離装置、(ε)が極小流量の1圧力制
御装置、げ)がガス減衰タンク、(g)が充填ラインで
、−次冷却材(軽水)中には、放射線による水分解(H
20→H2、Oz)を防ぐために、−次冷却材に水素ガ
スが意識的に含まれている。発生した放射性希ガスは一
次冷却材中に含まれ、抽出ライン(α)を−次冷却材及
び水素ガスとともに出て(る。これらの水素ガス及び放
射性希ガスは微量で、非凝縮性である。上記−次冷却材
は抽出ライン(α)を経て体積制御タンク(b)へ導か
れる。が、ここでは、水素ガス+A)を供給し、て、パ
ージすることにより、−次冷却材から放射性希ガスを抽
出し、またこの体積制御タンク(b>の気体空間から取
出した水素ガスを含む放射性希ガスをガス圧縮機(C1
)を経て水素分離装置向へ導き、ここで水素ガスを分離
、除去して、これをガス圧縮機(C2)を経て体積制御
タンクth)へ戻し、水素分離袋:t(dPF)残りの
放射性希ガスを圧力制御装置(e)を経てガス減衰タン
クJ)へ導いて、ここに貯蔵する一方、体積制御タンク
(b)内の一次冷却材を原子炉の一次冷却系へ戻して、
−次冷却材中の放射性希ガスの濃度低減及びプラントか
らの気体放出放射能量の低減を図りている。
A conventional light water reactor coolant degassing device is shown in Figure 1.2. First, to explain the coolant degassing device shown in Figure 1, (α)
is the cold material extraction line connected to the reactor's primary cooling system (
h) is a volume control tank, ('1) ('2) is a gas compressor, (d) is a hydrogen separator, (ε) is a pressure control device with minimal flow rate, ge) is a gas damping tank, (g) is the filling line, and the secondary coolant (light water) contains water splitting (H) due to radiation.
20→H2, Oz), hydrogen gas is intentionally included in the secondary coolant. The generated radioactive noble gas is contained in the primary coolant and exits the extraction line (α) together with the secondary coolant and hydrogen gas. These hydrogen gas and radioactive noble gas are in trace amounts and are non-condensable. The above-mentioned secondary coolant is led to the volume control tank (b) via the extraction line (α).However, here, by supplying hydrogen gas +A) and purging, radioactivity is removed from the secondary coolant. The rare gas is extracted, and the radioactive rare gas containing hydrogen gas taken out from the gas space of the volume control tank (b) is transferred to a gas compressor (C1).
) to the hydrogen separator, where the hydrogen gas is separated and removed, and returned to the volume control tank th) via the gas compressor (C2). conducting the noble gas via the pressure control device (e) to the gas attenuation tank J) and storing it there, while returning the primary coolant in the volume control tank (b) to the reactor primary cooling system;
- Efforts are being made to reduce the concentration of radioactive rare gases in the secondary coolant and the amount of radioactivity released from the plant.

次に第2図の冷却材脱ガス装置を説明すると、(a)(
b)(c)(7’l (7)が前記と同一の部分、(d
′)が水素再結合装置で、水素ガス及び放射性希ガスを
含む一次冷却材を抽出ライン(α)を経て体積制御タン
ク(b)へ導き、ここでは、水素ガス(A)を供給して
、−で−ジすることにより、−次冷却材から放射性希ガ
スを抽出し、またこの体積制御タンク(h)の勿体空間
から取出した水素ガスを含む放射性希ガスをガス圧縮機
(C)を経て水素再結合装置(cL’)へ導き、ここで
は、酸素ガス(B)を供給して、水素ガスを水(D)と
して取出し、残りの放射性希ガスをガス減衰タンクび)
へ導く一方、体積制御タンク(b)内の一次冷却材を原
子炉の一次冷却系へ戻して、−次冷却材中の放射性希ガ
スの濃度低減及びプラントからの気体放出放射能量の低
減を図っている。
Next, to explain the coolant degassing device shown in Fig. 2, (a) (
b) (c) (7'l (7) is the same part as above, (d
') is a hydrogen recombination device, in which a primary coolant containing hydrogen gas and a radioactive noble gas is guided through an extraction line (α) to a volume control tank (b), where hydrogen gas (A) is supplied, The radioactive rare gas is extracted from the secondary coolant by -, and the radioactive rare gas including hydrogen gas taken out from the waste space of this volume control tank (h) is passed through the gas compressor (C). Here, oxygen gas (B) is supplied, hydrogen gas is extracted as water (D), and the remaining radioactive rare gas is transferred to a gas attenuation tank (cL').
At the same time, the primary coolant in the volume control tank (b) is returned to the reactor primary cooling system to reduce the concentration of radioactive noble gas in the secondary coolant and the amount of radioactivity released from the plant. ing.

前記第1.2図の軽水炉の冷却材脱ガス装置では、原子
炉の一次冷却系から抽出した一次冷却材を体積制御タン
ク(h>へ導(一方、同タンク(h)へ水素カス(Aj
を供給して、パージすることにより、放射性希ガスを抽
出しているので、−・次冷却材中の放射性希ガスの濃度
低減効果に限度がある。、またプラント停止時には、原
子炉の一次冷却材系から抽出した一次冷却材を体積制御
タンク(b)へ轟<一方、同タンク(b)へ窒素ガスを
供給して、−ξ−ジすることにより、放射性希ガスを抽
出しているので、−次冷却材中の放射性希ガスの濃度を
低減するのに、長い時間を必要とするという問題があっ
た。
In the light water reactor coolant degassing device shown in Fig. 1.2, the primary coolant extracted from the primary cooling system of the reactor is guided to the volume control tank (h).
Since the radioactive rare gas is extracted by supplying and purging, there is a limit to the effect of reducing the concentration of the radioactive rare gas in the secondary coolant. Also, when the plant is shut down, the primary coolant extracted from the reactor primary coolant system is sent to the volume control tank (b).Meanwhile, nitrogen gas is supplied to the same tank (b) to Since the radioactive rare gas is extracted using the method, there is a problem in that it takes a long time to reduce the concentration of the radioactive rare gas in the secondary coolant.

本発明は前記の問題点に対処するもので、原子炉の一次
冷却系から受は入れた冷却材中のガスを冷却材から蒸気
により脱ガスする脱ガス塔と、同脱ガス塔の気体空間か
ら受は入れた蒸気を凝縮して上記脱ガス塔へ戻す第1の
凝縮器と、同第1の凝縮器からエゼクタを弁して受は入
れたガス中の蒸気を凝縮する第2の凝縮路とを具えてい
ることを特徴とした軽水炉の冷却材脱ガス装置に係り、
その目的とする処は、冷却材中の放射性希ガスの濃度低
減を効率よく迅速に行なえる。設(M費を低減できる。
The present invention addresses the above-mentioned problems and provides a degassing tower for degassing the gas in the coolant received from the primary cooling system of a nuclear reactor using steam from the coolant, and a gas space of the degassing tower. A first condenser that condenses the steam that is introduced into the receiver and returns it to the degassing tower, and a second condenser that condenses the vapor in the gas that is introduced into the receiver by valving an ejector from the first condenser. This invention relates to a coolant degassing device for a light water reactor characterized by having a
The purpose is to efficiently and quickly reduce the concentration of radioactive rare gases in the coolant. (M cost can be reduced.

メンテナンスを長期間不要にできる改良された軽水炉の
冷却材脱ガス装置を供する点にある。
An object of the present invention is to provide an improved coolant degassing device for a light water reactor that does not require maintenance for a long period of time.

次に前記軽水炉の冷却材脱ガス装置を第3図に示す一実
施例により説明すると、(1)が原子炉の一次冷却系に
接続した冷却材抽出ライン、(2)が体積制御タンク、
(3)が光重ライン、(3)が上記冷却材抽出ライン(
1)から分岐した冷却材抽出ライン、(4)か脱ガス塔
、(5)が同脱ガス塔(4)の気体空間から延びた蒸気
ライン、(6)が第1の凝縮器、(7)が同第1の凝縮
器(6)から延びたガスライン、(8)がエゼクタ、(
9)が第2の凝縮器、a(1)がエゼクタ、01)が第
2の凝縮器、(12)がエゼクタ、03)が第2の凝縮
器、aルが同第2の凝縮器u、(から′廃ガス系統(1
51へ延びた放射性希ガス(廃ガス)ライン、(lf3
1が上記第1の凝り器(6)から上記脱ガス塔(4)へ
延びた凝縮水ライン、(L7)が上記第1の凝縮器(6
)の冷却水う・rン、α報が上記第2の凝縮ビタ(9)
(II)Q31の冷却水ライン、(l湧が上記脱ガス塔
(4)から延びた冷却材ライン、Fjが循環ポンプ、(
2Dが同循環1ドンズ(20の吐出側から分岐した冷却
材う・「ン、(27Jが加熱器、(26)が同加熱訝C
2の補助蒸気ライン、 (23+が同加熱訴(nから上
記脱ガス塔(4)へ延びた蒸気ライン、(219が上記
循環ポンプ(20)の吐出側から上記体積制御タンク(
2)の上流側へ延びた冷却材ライン、(26+が同冷却
材ライン(24]から上記冷却材抽出ライン(3)へ延
びた冷却材ライン、06+が上記工ぞフタ(8)(+0
1叩へ延びた駆動蒸気ラインである。
Next, the light water reactor coolant degassing device will be explained with reference to an embodiment shown in FIG. 3. (1) is a coolant extraction line connected to the reactor primary cooling system, (2) is a volume control tank,
(3) is the light heavy line, (3) is the coolant extraction line (
A coolant extraction line branched from 1), (4) a degassing tower, (5) a steam line extending from the gas space of the degassing tower (4), (6) a first condenser, and (7) ) is the gas line extending from the first condenser (6), (8) is the ejector, (
9) is the second condenser, a (1) is the ejector, 01) is the second condenser, (12) is the ejector, 03) is the second condenser, a is the second condenser u , (from 'waste gas system (1
Radioactive noble gas (waste gas) line extending to 51, (lf3
1 is a condensed water line extending from the first condenser (6) to the degassing tower (4), and (L7) is a condensed water line extending from the first condenser (6) to the degassing tower (4).
)'s cooling water, the α information is the second condensed water (9)
(II) Cooling water line of Q31, (l well is a coolant line extending from the degassing tower (4), Fj is a circulation pump, (
2D is the same circulation 1 donz (coolant branched from the discharge side of 20) (27J is the heater, (26) is the same heating pipe C
2 auxiliary steam line (23+ is the steam line extending from the heating pump (n) to the degassing tower (4), (219 is the steam line extending from the discharge side of the circulation pump (20) to the volume control tank (
2), the coolant line (26+) is the coolant line that extends from the coolant line (24) to the coolant extraction line (3), and 06+ is the coolant line (8) (+0
This is a driving steam line that extends to one stroke.

次に前記軽水炉の冷却材脱ガス装置の作用を説明する。Next, the operation of the coolant degassing device for the light water reactor will be explained.

原子炉の一次冷却系から抽出さhた一次冷却材は、冷却
材抽出ライン(11(3)を経て脱ガス塔(4)へ導か
れて、スプレー状に噴霧される。一方、同脱ガス塔(4
)内の冷却材の一部は、冷却材ライン(1つ循環ボンズ
Cω冷却材ライン(2]Jを経て加熱器Czに導かれ、
ここで蒸気になり、蒸気ラインのを経て脱ガス塔(4)
へ導かれ、同蒸気により、上記冷却材抽出ライン(3]
から脱ガス塔(4)へ導かれた冷却材中からガス成分が
分離、除去される。また同脱ガス塔(4)の気体空間に
存在するガス成分を含む蒸気は、蒸気ライン(5)を経
て第1の凝縮器(6)へ導かれ、冷却水ライン(1ηの
冷却水により冷却されて、殆んどの蒸気が凝縮水になり
、凝縮水ラインμ6)を経て脱ガス塔(4)へ戻される
。このとき、駆動用蒸気ライン(26)から同第1の凝
縮器(6)の後流側のエゼクタ(8)(00)θり)へ
駆動用蒸気が噴射されており、同エゼクタ(8)内に負
圧が生じている。そのため、第1の凝縮器(6)内の蒸
気を含むガス成分はエゼクタ(8)へ吸引され、これが
駆動用蒸気とともに第2の凝縮器(9)へ導かれ、冷却
水ライン08)の冷却水により冷却されて、殆んどの蒸
気が凝縮水になり、それが第2の凝縮器(9)外へ取り
出される。また同第2の凝縮器(9)内の蒸気を含むガ
ス成分はエゼクタ(10)へ吸引され、これが駆動用蒸
気とともに第2の凝縮器θ1)へ導かれ、冷却水ライン
08)の冷却水により冷却されて、殆んどの蒸気が凝縮
水になり、それが第2の凝縮器0I外へ取り出される。
The primary coolant extracted from the reactor primary cooling system is led to the degassing tower (4) through the coolant extraction line (11 (3)) and is sprayed in the form of a spray. Tower (4
) is led to the heater Cz via the coolant line (one circulation bond Cω coolant line (2)J),
Here it becomes steam and passes through the steam line to the degassing tower (4)
The steam is guided to the coolant extraction line (3).
Gas components are separated and removed from the coolant that is led to the degassing tower (4). In addition, the steam containing gas components present in the gas space of the degassing tower (4) is led to the first condenser (6) via the steam line (5), and is cooled by a cooling water line (1η of cooling water). Most of the steam becomes condensed water and is returned to the degassing tower (4) via the condensed water line μ6). At this time, driving steam is injected from the driving steam line (26) to the ejector (8) (00) θ) on the downstream side of the first condenser (6), and the driving steam There is negative pressure inside. Therefore, the gas component containing steam in the first condenser (6) is sucked into the ejector (8), which is led together with the driving steam to the second condenser (9) to cool the cooling water line 08). Cooled by water, most of the steam becomes condensed water, which is taken out of the second condenser (9). In addition, the gas component containing steam in the second condenser (9) is sucked into the ejector (10), which is led together with the driving steam to the second condenser θ1), where the cooling water in the cooling water line 08) is Most of the steam becomes condensed water, which is taken out of the second condenser 0I.

また同第2の凝縮器01)内の蒸気を含むガス成分はエ
ゼクタ(121へ吸引され、これが駆動用蒸気とともに
第2の凝、縮5(13)へ導かれ、冷却水ライン(1涌
の冷却水により冷却されて、殆んどの蒸気が凝縮水にな
り、それが第2の凝縮Rat13)外へ取り出される。
In addition, the gas component containing steam in the second condenser 01) is sucked into the ejector (121), which is led together with the driving steam to the second condenser 5 (13), where the cooling water line (1 Cooled by cooling water, most of the steam becomes condensed water, which is taken out to the outside of the second condensing Rat 13).

また同第2の凝縮?、% (13i内のガス成分は、最
終段のエゼクタaりの噴射圧力を駆動圧力(約0.5 
kl? /の2G)とじて廃ガス処理系統へ送られる。
Also the same second condensation? , % (The gas component in 13i is the driving pressure (approximately 0.5
kl? /2G) and sent to the waste gas treatment system.

また上記脱ガス塔(4)内で脱ガスされた冷却材は、循
環ポンプ(20)冷却材C位捲経て体積制御タンク(2
)へ送られる。が、一部の冷却材は、脱ガス塔(4)へ
の冷却材流入量を一定に保つために、冷却材ライン00
を経て冷却材抽出ライン(3)へ戻される。
In addition, the coolant degassed in the degassing tower (4) passes through the circulation pump (20), the coolant C position, and the volume control tank (2).
). However, in order to keep the amount of coolant flowing into the degassing tower (4) constant, some coolant is passed through the coolant line 00.
and is returned to the coolant extraction line (3).

本発明の軽水炉の冷却材脱ガス装置は前記のようにガス
成分を含む冷却材を脱ガス塔(4)へ導いて、冷却材中
のガス成分を蒸気により分離、除去する一方、駆動用蒸
気をエゼクタ(8)QO)(12+へ噴射し、同もエゼ
クタ(8)00)(12)上流側の凝縮器(6)(9)
Qli 内(1) M ’Aを含むガス成分を吸引し、
これらの凝縮器内を負正にした状態で蒸気の凝縮を行な
って、ガス成分中の蒸気を分離、除去するようにしてお
り、冷却材中の放射性希ガスの濃度低減を効率よく迅速
に行なえる効果がある。また負圧発生装置に構造簡単な
エゼクタを使用しており、真空ポンプを使用する場合に
比べると設fii費を低減できる。またエゼクタには、
真空ポンプのように回転部分がなくて、メンテナンスを
長期間不要にできる。また負圧発生装置が吸引するガス
は、その殆んどが水素ガスであるため、真空ポンプの場
合には、空気の混入を防燥上防止する必要があるが、エ
ゼクタの場合には、その必要がな(て、この点からも設
備費を低減できる。また最終段エゼクタに噴射した駆動
蒸気圧力を、分離、除去した放射性希ガスを廃ガス処理
系統へ送る流体駆動圧力にすることができ、放射性希ガ
ス(廃ガス)移送用ブロアを不要にできて、この点から
も設備費を低減できる効果がある。
The coolant degassing device for a light water reactor of the present invention, as described above, guides the coolant containing gas components to the degassing tower (4) to separate and remove the gas components in the coolant with steam. is injected to the ejector (8) QO) (12+, which is also ejector (8) 00) (12) and the upstream condenser (6) (9).
Inside Qli (1) Aspirate the gas component containing M'A,
Steam is condensed with the inside of these condensers turned negative and positive to separate and remove the steam in the gas components, making it possible to efficiently and quickly reduce the concentration of radioactive rare gases in the coolant. It has the effect of Furthermore, an ejector with a simple structure is used as the negative pressure generating device, and the installation cost can be reduced compared to the case where a vacuum pump is used. Also, the ejector has
Unlike vacuum pumps, there are no rotating parts, making maintenance unnecessary for a long time. In addition, most of the gas sucked by the negative pressure generator is hydrogen gas, so in the case of a vacuum pump, it is necessary to prevent air from entering, but in the case of an ejector, it is necessary to prevent air from entering. In addition, the driving steam pressure injected into the final stage ejector can be used as the fluid driving pressure to send the separated and removed radioactive rare gas to the waste gas treatment system. This eliminates the need for a blower for transporting radioactive rare gas (waste gas), which also has the effect of reducing equipment costs.

以上本発明を実施例について説明したが、勿論本発明は
このような実施例にだけ局限されるものではなく、本発
明の精神を逸脱しない範囲内で種々の設計の改変を施し
うるものである。
Although the present invention has been described above with reference to embodiments, it goes without saying that the present invention is not limited to such embodiments, and that various design modifications can be made without departing from the spirit of the present invention. .

【図面の簡単な説明】[Brief explanation of drawings]

第1.2図は従来の軽水炉の冷却材脱ガス装置を示す系
統図、第6図は本発明に係る軽水炉の冷却材脱ガス装置
の一笑格例を示す系統図である。 (4)−−一説ガス塔、(61−−一第1の凝縮器、(
8!(10)(2)−m−エゼクタ、(9)Ql)(t
3! −−一第2の凝縮器。 復代理人 弁理士開本重文 り12名
FIG. 1.2 is a system diagram showing a conventional light water reactor coolant degassing device, and FIG. 6 is a system diagram showing an example of a light water reactor coolant degassing device according to the present invention. (4)--One theory gas tower, (61--1st condenser, (
8! (10)(2)-m-ejector, (9)Ql)(t
3! --First and second condenser. Sub-agents: 12 patent attorneys who are important to Kaimoto

Claims (1)

【特許請求の範囲】[Claims] 原子炉の一次冷却系から受は入れた冷却材中のガスを冷
却材から蒸気により脱ガスする脱ガス塔と、同脱ガス塔
の気体空間から受は入れた蒸気を凝縮して上記脱ガス塔
へ戻す第1の凝縮器と、同第1の凝縮器からエゼクタを
介して受は入れたガス中の蒸気を凝縮する第2の凝縮器
とを具えていることを特徴とした軽水炉の冷却材脱ガス
装置。
A degassing tower that degass the gas in the coolant received from the reactor primary cooling system by using steam from the coolant, and a degassing tower that condenses the steam received from the gas space of the degassing tower to degas the gas. Cooling of a light water reactor characterized by comprising a first condenser that returns to the tower, and a second condenser that condenses vapor in gas received from the first condenser via an ejector. Material degassing equipment.
JP58032927A 1983-03-02 1983-03-02 Coolant degassing device in light water reactor Pending JPS59159097A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58032927A JPS59159097A (en) 1983-03-02 1983-03-02 Coolant degassing device in light water reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58032927A JPS59159097A (en) 1983-03-02 1983-03-02 Coolant degassing device in light water reactor

Publications (1)

Publication Number Publication Date
JPS59159097A true JPS59159097A (en) 1984-09-08

Family

ID=12372539

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58032927A Pending JPS59159097A (en) 1983-03-02 1983-03-02 Coolant degassing device in light water reactor

Country Status (1)

Country Link
JP (1) JPS59159097A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5740264A (en) * 1995-08-29 1998-04-14 Foster Electric Co., Ltd. Miniature electroacoustic transducer
CN103778973A (en) * 2012-10-22 2014-05-07 中国核动力研究设计院 Controllable pressure releasing system for integral reactor

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5740264A (en) * 1995-08-29 1998-04-14 Foster Electric Co., Ltd. Miniature electroacoustic transducer
DE19633097C2 (en) * 1995-08-29 1999-02-18 Foster Electric Co Ltd Miniaturized electro-acoustic transducer
CN103778973A (en) * 2012-10-22 2014-05-07 中国核动力研究设计院 Controllable pressure releasing system for integral reactor

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